CN218038595U - Radioactive waste liquid treatment system - Google Patents

Radioactive waste liquid treatment system Download PDF

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CN218038595U
CN218038595U CN202221729725.0U CN202221729725U CN218038595U CN 218038595 U CN218038595 U CN 218038595U CN 202221729725 U CN202221729725 U CN 202221729725U CN 218038595 U CN218038595 U CN 218038595U
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radioactivity
decay
radioactive
waste liquid
sealed
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巴建涛
李立君
李霞
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Abstract

The utility model belongs to the technical field of environment radioactivity monitoring facilities, in particular to relate to the processing technology field of nuclear facility place radioactivity waste liquid to nuclear medicine branch of academic or vocational study, isotope laboratory etc., concretely relates to radioactivity waste liquid processing system. The utility model discloses consider from a plurality of aspects such as screening, automatic monitoring, convenient and practical of radioactive waste liquid respectively, handle nuclear medicine branch of academic or vocational study radioactive waste liquid. The waste liquid is distinguished and screened, and the low-radioactivity waste liquid which does not need to decay for a long time is separated, so that the utilization efficiency of the decay tank is greatly improved; the radioactivity is measured in an active detection area, so that the working efficiency is remarkably improved, and the irradiated dose of personnel is reduced. The utility model discloses can popularize and apply to nuclear facilities such as isotope production, nuclear industry application place, to improving decay pond availability factor, practicing thrift engineering cost, reduce personnel and be irradiated the dose and protect the environment and have the significance.

Description

Radioactive waste liquid treatment system
Technical Field
The utility model relates to an environmental radioactivity monitoring technology field, especially to involving nuclear facility place radioactive waste liquid's processing technology field such as nuclear medicine branch of academic or vocational study, isotope laboratory, concretely relates to radioactive waste liquid processing system.
Background
The diagnosis and treatment by using the unique advantages of medical isotopes is an indispensable important means for improving the health level of people of 24484m. In the aspect of diagnosis, the medical isotope can provide information such as molecular level blood flow, function, metabolism and the like of a human body, and early diagnosis is carried out on pathological changes which do not have morphological structure changes; in the aspect of treatment, the medical isotope can kill lesion tissues by utilizing the radioactivity of the medical isotope, so that the precise removal of tiny focuses is realized, and a better treatment effect is achieved. Promotion of high-quality development of medical isotopes is significant for promotion of Chinese construction of 24484kan.
In the process of radioactive diagnosis and treatment in nuclear medicine, a large amount of radioactive waste liquid is generated, and mainly includes excrement generated after a patient takes or injects a radioactive isotope, radioactive waste liquid discharged from containers, cups and laboratories for subpackaging and injecting the isotope, and labeled compounds. Radioactive waste liquid contains radionuclides such as I-131, F-18, tc-99m and the like, so that the radioactive waste liquid has large influence on the environment and cannot be directly discharged. Radioactive waste liquid is collected and stored through a decay tank, and can be discharged after reaching the standard through natural decay. Wherein, the temporary storage time of the radioactive waste liquid containing nuclide with half-life period less than 24 hours exceeds 30 days, and then the radioactive waste liquid can be directly discharged; the temporary storage time of the radioactive waste liquid containing nuclide with the half-life period of more than 24 hours exceeds 10 times of the longest half-life period (the temporary storage time of the nuclide containing I-131 exceeds 180 days), and the monitoring result is approved by a tube inspection door and then is discharged according to a specified mode. The total alpha of the total discharge ports of the radioactive waste liquid is not more than 1Bq/L, the total beta is not more than 10Bq/L, and the concentration of the radioactivity of I-131 is not more than 10Bq/L.
At present, the conventional treatment method of radioactive waste liquid in the nuclear medicine department of hospitals comprises the following steps: firstly, radioactive waste liquid generated in the outpatient service and ward diagnosis and treatment process is directly discharged to a decay tank through a pipeline. The decay pond is provided with a plurality of boxes, and a decay pond decay is arranged into earlier to the waste liquid, closes when the waste liquid is nearly full and seals up the deposit, waits for its natural decay to reach the emission requirement. Then, the second decay pool is opened for the waste liquid to be discharged for use, and the like is repeated. And when the requirement of decay time is met, extracting a water sample from the decay tank, sending the water sample to a laboratory for analysis, and after the radioactivity of the water sample is confirmed to meet the discharge requirement, discharging waste liquid in the decay tank to a hospital medical waste liquid tank, and finally, merging the waste liquid into a municipal sewage pipe network.
The above treatment methods mainly have the following problems: 1. the capacity requirement of the decay tank is getting bigger and bigger. The radioactive waste liquid can not be used in the temporary storage period due to long temporary storage time, for example, the temporary storage time of the I-131 nuclide exceeds 180 days; and along with the patient is more and more, the waste liquid of production is also more and more, especially during the patient is in hospital, also remit the decay pond in the bathing water, greatly increased decay pond volume demand, all higher and higher to decay pond place space and construction cost requirement. 2. The automation degree of radioactive waste liquid treatment is not high. At present, most of the measurement processes adopt a method of manual sampling and laboratory analysis, the overall efficiency is not high, and the irradiation dose of workers is increased.
SUMMERY OF THE UTILITY MODEL
In view of this, the utility model provides a radioactive liquid waste treatment system considers from a plurality of aspects such as screening, automatic monitoring, convenient and practical of radioactive liquid waste respectively, handles nuclear medicine branch of academic or vocational study radioactive liquid waste. Waste liquid is distinguished and screened, and low-radioactivity waste liquid which does not need to decay for a long time is separately treated, so that the utilization efficiency of a decay tank is greatly improved; the activity is measured in an active detection area, so that the working efficiency is remarkably improved, and the irradiated dose of personnel is reduced. The utility model discloses can popularize and apply to nuclear facilities such as isotope production, nuclear industry application place, to improving decay pond availability factor, practicing thrift engineering cost, reduce personnel and be irradiated the dose and protect the environment and have the significance.
In order to realize the technical purpose, the utility model discloses the concrete technical scheme who adopts is:
a radioactive waste liquid treatment system for treating radioactive site-related waste liquid, comprising:
a low-radioactivity settling zone, wherein estimated low-radioactivity waste liquid in the waste liquid is introduced;
a high-radioactivity settling area, wherein estimated high-radioactivity waste liquid in the waste liquid is introduced;
the high radioactivity decay pool is filled with the upper liquid of the high radioactivity settling zone;
an activity detection zone, wherein the upper layer liquid of the low-radioactivity sedimentation zone is introduced, and a radioactivity measuring device is arranged;
wherein the radioactive waste liquid treatment system further comprises a low radioactive decay tank; when the measurement result of the radioactivity measuring device is lower than a preset value, the upper liquid of the low-radioactivity sedimentation area is introduced into the low-radioactivity decay pool; and when the measurement result of the radioactivity measurement device is higher than a preset value, the upper liquid of the low-radioactivity sedimentation area is introduced into the high-radioactivity decay tank.
Further, the high radioactive decay cell and/or the low radioactive decay cell comprise:
a sealed decay tank for containing the supernatant liquid of the low-activity settling zone and/or the high-activity settling zone;
a decay tank inlet communicating the sealed decay tank with the low-radioactivity settling zone and/or the high-radioactivity settling zone;
the air outlet is arranged on the sealed decay tank, is communicated with the sealed decay tank and is provided with an opening and closing valve;
the medicine filling port is arranged on the sealed decay tank, is communicated with the sealed decay tank and is provided with an opening and closing valve;
a reamer disposed in the sealed decay tank;
and the outlet of the decay tank is communicated with the sealed decay tank and is provided with an opening and closing valve.
Furthermore, a liquid level meter for measuring the liquid level in the sealed decay tank is arranged on the sealed decay tank.
Furthermore, a medicine filling port for adding a medicament into the sealed decay tank is also arranged on the sealed decay tank.
Furthermore, a water spray nozzle for adding dilution water and/or flushing water into the sealed decay tank is arranged on the sealed decay tank.
Furthermore, a sampling port for collecting samples in the self-sealing decay tank is also arranged on the sealing decay tank.
Furthermore, an activity measuring pipeline for sampling and measuring waste liquid in the sealed decay tank is also arranged on the sealed decay tank; and the inlet of the activity measuring pipeline is communicated with the sealed decay tank, and the outlet of the activity measuring pipeline is communicated with the outlet of the decay tank.
Further, the low radioactive decay pool is connected with the low radioactive sedimentation area and the high radioactive sedimentation area on the basis of pipelines provided with valves.
Furthermore, the high radioactive decay pool is connected with the low radioactive sedimentation area through a pipeline provided with a valve.
Adopt above-mentioned technical scheme, the utility model discloses following beneficial effect can also be brought:
the utility model discloses set up sedimentation tank, reamer and water jet, can not take place the foreign matter and block up in making the transportation of radioactive waste liquid, further improved the treatment effeciency and avoided personnel to receive unnecessary radiation dose.
Drawings
In order to more clearly illustrate the technical solutions of the embodiments of the present invention, the drawings required to be used in the embodiments will be briefly described below, it is obvious that the drawings in the following description are only some embodiments of the present invention, and it is obvious for those skilled in the art that other drawings can be obtained according to the drawings without creative efforts.
FIG. 1 is a general structure diagram of a radioactive waste liquid treatment system according to an embodiment of the present invention;
fig. 2 is a structure diagram of a high radioactive decay tank and/or a low radioactive decay tank in the embodiment of the present invention;
FIG. 3 is a flow chart of a radioactive liquid waste treatment method according to an embodiment of the present invention;
wherein: 1. an inlet of the decay tank; 2. sealing the decay tank; 3. a drug filling port; 4. an exhaust port; 5. a liquid level gauge; 6. a reamer; 7. an activity measuring pipeline; 8. a water jet; 9. a sampling port; 10. and (4) an outlet of the decay tank.
Detailed Description
The following describes embodiments of the present invention in detail with reference to the accompanying drawings.
The following description of the embodiments of the present invention is provided for illustrative purposes, and other advantages and effects of the present invention will be readily apparent to those skilled in the art from the disclosure herein. It is to be understood that the embodiments described are only some embodiments of the invention, and not all embodiments. The present invention can also be implemented or applied through other different specific embodiments, and various details in the present specification can be modified or changed based on different viewpoints and applications without departing from the spirit of the present invention. It should be noted that the features in the following embodiments and examples may be combined with each other without conflict. Based on the embodiments in the present invention, all other embodiments obtained by a person skilled in the art without creative efforts belong to the protection scope of the present invention.
It is noted that various aspects of the embodiments are described below within the scope of the appended claims. It should be apparent that the aspects described herein may be embodied in a wide variety of forms and that any specific structure and/or function described herein is merely illustrative. Based on the disclosure, one skilled in the art should appreciate that one aspect described herein may be implemented independently of any other aspects and that two or more of these aspects may be combined in various ways. For example, an apparatus may be implemented and/or a method practiced using any number of the aspects set forth herein. Additionally, such an apparatus may be implemented and/or such a method may be practiced using other structure and/or functionality in addition to one or more of the aspects set forth herein.
It should be noted that the drawings provided in the following embodiments are only for illustrating the basic idea of the present invention, and the drawings only show the components related to the present invention rather than being drawn according to the number, shape and size of the components in actual implementation, and the form, amount and ratio of the components in actual implementation may be changed at will, and the layout of the components may be more complicated.
In addition, in the following description, specific details are provided to facilitate a thorough understanding of the examples. However, it will be understood by those skilled in the art that the aspects may be practiced without these specific details.
In an embodiment of the present invention, as shown in fig. 1, a radioactive liquid waste treatment system is provided for treating radioactive site liquid waste, comprising:
the low-radioactivity settling zone is a sludge pool, and estimated low-radioactivity waste liquid is introduced into the waste liquid;
the high-radioactivity settling zone is a sludge tank, and estimated high-radioactivity waste liquid is introduced into the waste liquid;
the high radioactivity decay pool is filled with the upper liquid of the high radioactivity settling zone;
an activity detection zone, wherein the upper layer liquid of the low-radioactivity sedimentation zone is introduced, and a radioactivity measuring device is arranged;
wherein, the radioactive waste liquid treatment system also comprises a low radioactive decay pool; when the measurement result of the radioactivity measuring device is lower than a preset value, the upper liquid of the low radioactivity sedimentation area is introduced into the low radioactivity decay pool; and when the measurement result of the radioactivity measuring device is higher than the preset value, the upper liquid of the low-radioactivity settling area is introduced into the high-radioactivity decay tank.
In this embodiment, the radioactive waste liquid treatment system generally includes two circuits: a high-radioactivity waste liquid treatment loop and a low-radioactivity waste liquid treatment loop. The high radioactive waste liquid is mainly from excrement generated after a patient takes or injects radioactive isotopes, washing water of containers, cups and laboratories for subpackaging and injecting the isotopes, radioactive waste liquid discharged by labeled compounds and the like in the radioactive diagnosis and treatment process. The low-radioactivity waste liquid mainly comes from waste liquid generated by bathing of a patient.
As shown in figure 1, the high-radioactivity waste liquid treatment loop comprises a buffer zone and a decay zone, wherein the buffer zone is provided with a plurality of sedimentation tanks which can be alternately used. The decay zone is provided with a high radioactive decay cell and an activity measuring device.
As shown in figure 1, the low-radioactivity waste liquid treatment loop comprises a buffer measurement area and a decay area, wherein the buffer area is provided with a sedimentation tank, a sampling tank and a measurement tank, and the sedimentation tank, the sampling tank and the measurement tank can be arranged into a plurality of groups for alternate use. The decay zone is provided with a low radioactive decay cell and an activity measuring device.
As shown in figure 1, radioactive waste is passed through two processing circuits, waiting for decay in the decay zone and discharging into hospital medical waste pool after activity measurement is passed.
As shown in figure 2, the upper part of the outside of the decay tank comprises a radioactive waste liquid inlet, a medicine filling port 3 and an exhaust port 4. The radioactive waste liquid inlet is provided with a manual valve and an electromagnetic valve, and the medicine filling port 3 and the exhaust port 4 are provided with manual valves. The top of the inner part of the decay tank is provided with a liquid level measuring device, and the lower part of the inner part of the decay tank is in an inverted cone shape and is provided with a reamer 6. A radioactivity measuring pipeline 7, a radioactive waste liquid outlet, a water spraying port 8 and a sampling port 9 are arranged below the outside of the decay tank. A manual valve and an electromagnetic valve are arranged above the radioactivity activity measuring pipeline 7, and an electromagnetic valve is arranged below the radioactivity activity measuring pipeline. A manual valve and an electromagnetic valve are arranged at the radioactive waste liquid outlet. The water spraying opening 8 is provided with a manual valve. The sampling port 9 is provided with a pressure reducing valve and a manual valve.
FIG. 3 is a flow chart of a radioactive liquid waste treatment method. And sampling and measuring the low-radioactivity waste liquid in a buffer measurement area, acquiring the radioactivity value of the waste liquid in the buffer area, and if the result is low radioactivity, discharging the low-radioactivity waste liquid into a low-radioactivity decay pool under the control of an electromagnetic valve. If the result is high radioactivity, the high radioactivity is discharged into a high radioactivity decay pool under the control of an electromagnetic valve. The waste liquid naturally decays in the decay tank, and the radioactivity is gradually reduced. The radioactive activity value is measured by the decay tank, and if the radioactive activity value reaches the discharge standard, the waste liquid is discharged into the medical waste liquid tank through the electromagnetic valve.
As shown in fig. 3, the high radioactivity waste liquid passes through the buffer zone and directly enters the high radioactivity decay tank, and the waste liquid naturally decays in the decay tank to gradually reduce radioactivity. The radioactive activity value is measured by the decay tank, and if the radioactive activity value reaches the discharge standard, the waste liquid is discharged into the medical waste liquid tank through the electromagnetic valve.
In this embodiment, the high and/or low radioactive decay reservoirs include:
a sealed decay tank 2 for containing the upper liquid of the low-activity sedimentation zone and/or the high-activity sedimentation zone;
a decay pool inlet 1 which is communicated with the sealed decay pool 2 and the low-radioactivity settling zone and/or the high-radioactivity settling zone;
the exhaust port 4 is arranged on the sealed decay tank 2, is communicated with the sealed decay tank 2 and is provided with an opening and closing valve;
the medicine filling port 3 is arranged on the sealed decay tank 2, is communicated with the sealed decay tank 2 and is provided with an opening and closing valve;
a reamer 6 disposed in the sealed decay tank 2;
the decay pool outlet 10 is communicated with the sealed decay pool 2 and is provided with an opening and closing valve.
In this embodiment, a liquid level gauge 5 for measuring the liquid level in the sealed decay tank 2 is also arranged on the sealed decay tank 2.
In this embodiment, the sealed decay tank 2 is further provided with a drug filling port 3 for adding a drug into the sealed decay tank 2.
In this embodiment, the sealed decay tank 2 is further provided with a water jet 8 for adding dilution and/or rinsing water to the sealed decay tank 2.
In this embodiment, the sealed cell 2 is further provided with a sample port 9 for collecting a sample from the sealed cell 2.
In this embodiment, the sealed decay tank 2 is further provided with an activity measuring pipeline 7 for sampling and measuring waste liquid in the sealed decay tank 2; the inlet of the activity measuring pipeline 7 is communicated with the sealed decay tank 2, and the outlet is communicated with the outlet 10 of the decay tank.
In this embodiment, the low radioactive decay tank is connected with the low radioactive settling area and the high radioactive settling area through pipelines provided with valves.
In this embodiment, the high radioactive decay tank is connected with the low radioactive settling zone based on a pipeline provided with a valve.
In one embodiment, a radioactive waste liquid treatment method based on the radioactive waste liquid treatment device is further provided, and the radioactive waste liquid treatment method comprises the following steps:
s101, dividing the production waste liquid into pre-estimated low-radioactivity waste liquid and pre-estimated high-radioactivity waste liquid according to the production process;
s102, introducing the estimated low-radioactivity waste liquid into a low-radioactivity settling zone, and conveying the high-radioactivity waste liquid into a high-radioactivity settling zone;
s103, detecting the radioactivity of the upper liquid in a low-radioactivity sedimentation zone based on the sampling detection zone; if the radioactivity is higher than the preset value, introducing the waste liquid in the low-radioactivity settling zone into a high-radioactivity attenuation pool, and if the radioactivity is lower than the preset value, introducing the waste liquid in the low-radioactivity settling zone into a low-radioactivity attenuation pool; introducing the upper liquid of the high-radioactivity settling area into a high-radioactivity decay pool;
and S104, detecting the liquid radioactivity in the low radioactive decay pool and the high radioactive decay pool at intervals, and discharging the liquid in the low radioactive decay pool and/or the high radioactive decay pool into a conventional waste liquid pool when the radioactivity is qualified.
This embodiment is used for right the utility model discloses a patent technical scheme's explanation, the technical personnel in the field basis the utility model discloses the change that is different from this embodiment that technical scheme made all belongs to the utility model discloses a protection scope.
The utility model is further explained as follows:
in the radioactive diagnosis and treatment process of the nuclear medicine department, a large amount of radioactive waste liquid is generated, the influence on the environment is large, and the radioactive waste liquid cannot be directly discharged. At present, the following problems mainly exist in the treatment process of radioactive waste liquid in the nuclear medicine department of hospitals: 1. the capacity requirement of the decay tank is getting bigger and bigger. The radioactive waste liquid can not be used in the temporary storage period due to long temporary storage time, for example, the temporary storage time of the I-131 nuclide exceeds 180 days; and along with the patient is more and more, the waste liquid of production is also more and more, especially during the patient is in hospital, also remit the decay pond in the bathing water, greatly increased decay pond volume demand, all higher and higher to decay pond place space and construction cost requirement. 2. The automation degree of radioactive waste liquid treatment is not high. At present, most of the measurement processes adopt a method of manual sampling and laboratory analysis, the overall efficiency is not high, and the irradiation dose of workers is increased. 3. The radioactive waste liquid treatment design is not scientific and perfect. At present, most of decay ponds are underground and generally have insufficient attention, and the decay ponds constructed in the early stage have various problems of inconvenient cleaning, sludge accumulation, waste blockage and the like in use, and need to be solved urgently.
In recent years, the development of nuclear medicine science is rapid, and a large number of new nuclear medicine departments are about to be built. Therefore, the radioactive waste liquid generated in the diagnosis and treatment process is reasonably and effectively treated, and the scientific discharge has important significance.
The measurement device and the measurement method described in this embodiment not only consider the main problems existing in the treatment process of the radioactive liquid waste in the nuclear medicine science, but also consider the practical requirements in practical use, and can effectively improve the use efficiency of radioactive liquid waste treatment and reduce the workload and the irradiated dose of workers.
As shown in fig. 1, the present embodiment generally includes two loops: a high-radioactivity waste liquid treatment loop and a low-radioactivity waste liquid treatment loop. The high radioactive waste liquid is mainly from excrement generated after a patient takes or injects radioactive isotopes, washing water of containers, cups and laboratories for subpackaging and injecting the isotopes, radioactive waste water discharged by labeled compounds and the like in the radioactive diagnosis and treatment process. The low-radioactivity waste liquid mainly comes from waste water generated by bathing of patients.
As shown in figure 1, the high-radioactivity waste liquid treatment loop comprises a buffer zone and a decay zone, wherein the buffer zone is provided with two sedimentation tanks, and the two sedimentation tanks are automatically controlled by electromagnetic valves and are respectively and alternately used. Waste liquid in the sedimentation tank is pumped to a decay area by a submersible sewage pump, and the operation of the submersible sewage pump is automatically controlled by the system. The decay zone is provided with three groups of high radioactive decay tanks and activity measuring devices, and the three groups of high radioactive decay tanks are automatically controlled by electromagnetic valves and are respectively used alternately. The waste liquid firstly gets into No. 1 decay pond, when pouring into the waste liquid and reaching the control liquid level of settlement, closes No. 1 decay pond and pours into the solenoid valve into, opens No. 2 decay pond and pours into the solenoid valve into, and radioactive waste liquid gets into No. 2 decay ponds. When the injected waste liquid reaches the set control liquid level, the number 2 decay pool injection electromagnetic valve is closed, the number 3 decay pool injection electromagnetic valve is opened, and the radioactive waste liquid enters the number 3 decay pool. Every group decay pond is equipped with activity measuring device, and when the decay pond reached decay time, if after 180 days, activity measuring device measured the waste liquid activity in corresponding the decay pond, if reach emission standard, system control solenoid valve is with the waste liquid drainage into medical wastewater.
As shown in figure 1, the low-radioactivity waste liquid treatment loop comprises a buffer memory measurement area and a decay area, wherein the buffer memory area is provided with two sets of sedimentation tanks, sampling tanks and measurement tanks, output ends of the two sets of sedimentation tanks are communicated, and the system controls the sedimentation tanks to output to a No. 1 sampling tank or a No. 2 sampling tank through electromagnetic valves. The rear ends of the two groups of sampling pools are provided with activity measuring devices, and the activity measuring devices judge the radioactivity of the waste liquid in the sampling pools. If the result is low radioactivity, the low radioactivity is discharged into a low radioactivity decay pool through the control of a solenoid valve. If the result is high radioactivity, the high radioactivity is discharged into a high radioactivity decay pool under the control of an electromagnetic valve.
As shown in fig. 1, the radioactive waste liquid passes through two processing loops, and is in a high radioactive decay pool and a low radioactive decay pool of a decay area, and waits for a period of time, so that the natural decay of the radioactive waste liquid reduces the radioactivity. And after the set time is reached, measuring the radioactivity of the waste liquid in the decay tank, if the measured activity reaches the standard, discharging the activity into a medical wastewater tank of a hospital through electromagnetic valve control, and if the activity does not reach the standard, continuously waiting until the activity reaches the standard, and then discharging the activity into the medical wastewater tank.
As shown in figure 2, the upper part of the outside of the decay tank comprises a radioactive waste liquid inlet, a medicine filling port 3 and an exhaust port 4. The radioactive waste liquid inlet is provided with a manual valve and an electromagnetic valve, and the medicine filling port 3 and the exhaust port 4 are provided with manual valves. The radioactive waste liquid enters the decay tank from the inlet, and the medicine filling port 3 is used for filling medicines such as NaOH and the like and balancing acidity and alkalinity in the decay tank. The exhaust port 4 is used for releasing methane in the excrement decay pond and has the effects of pressure reduction and flame retardance. Become the inside top of pond and be equipped with level measurement device, decay pond inside below is the back taper to be equipped with reamer 6. The liquid level measuring device judges the volume of waste liquid injected into the decay tank in real time and is used for informing the system to switch the volume of the waste liquid injected into the decay tank by the electromagnetic valve. The reamer 6 cuts and decomposes sundries such as paper towels, cloth strips and the like, and prevents radioactive pollution sources from solidifying and the drainage outlet from being blocked. A radioactivity measuring pipeline 7, a radioactive waste liquid outlet, a water spraying port 8 and a sampling port 9 are arranged below the outside of the decay tank. A manual valve and an electromagnetic valve are arranged above the radioactivity measuring pipeline 7, and an electromagnetic valve is arranged below the radioactivity measuring pipeline. The system controls the measurement of the activity of the waste liquid through an electromagnetic valve. And a manual valve and an electromagnetic valve are arranged at the radioactive waste liquid outlet and connected to a medical wastewater pool. The water spraying port 8 is provided with a manual valve and a high-speed water spraying inlet to prevent radioactive pollution sources from being solidified in the excrement decay tank. The sampling port 9 is provided with a pressure reducing valve and a manual valve and is used for manual waste liquid sample collection.
FIG. 3 is a flow chart of a radioactive liquid waste treatment method. And sampling and measuring the low-radioactivity waste liquid in a buffer measurement area, acquiring the radioactivity value of the waste liquid in the buffer measurement area, and if the result is low radioactivity, discharging the low-radioactivity waste liquid into a low-radioactivity decay pool under the control of an electromagnetic valve. If the result is high radioactivity, the high radioactivity is discharged into a high radioactivity decay pool under the control of a solenoid valve. The waste liquid naturally decays in the decay tank, and the radioactivity is gradually reduced. The radioactive activity value is measured by a decay tank, and if the radioactive activity value reaches the discharge standard, the waste liquid is discharged into a medical wastewater pool through an electromagnetic valve.
As shown in fig. 3, the high radioactivity waste liquid passes through the buffer zone and directly enters the high radioactivity decay tank, and the waste liquid naturally decays in the decay tank to gradually reduce radioactivity. The radioactive activity value is measured by the decay tank, and if the radioactive activity value reaches the discharge standard, the waste liquid is discharged into the medical wastewater tank through the electromagnetic valve.
The above description is only for the specific embodiments of the present invention, but the protection scope of the present invention is not limited thereto, and any changes or substitutions that can be easily conceived by those skilled in the art within the technical scope of the present invention should be covered by the protection scope of the present invention. Therefore, the protection scope of the present invention shall be subject to the protection scope of the claims.

Claims (9)

1. A radioactive liquid waste treatment system for treating radioactive site liquid waste, comprising:
a low-radioactivity settling zone, wherein estimated low-radioactivity waste liquid in the waste liquid is introduced;
a high-radioactivity settling area, wherein estimated high-radioactivity waste liquid in the waste liquid is introduced;
the high radioactivity decay pool is filled with the upper liquid of the high radioactivity settling zone;
an activity detection zone, wherein the upper layer liquid of the low-radioactivity sedimentation zone is introduced, and a radioactivity measuring device is arranged;
wherein the radioactive waste liquid treatment system further comprises a low radioactive decay tank; when the measurement result of the radioactivity measuring device is lower than a preset value, the upper liquid of the low-radioactivity sedimentation area is introduced into the low-radioactivity decay pool; and when the measurement result of the radioactivity measuring device is higher than a preset value, the upper layer liquid of the low-radioactivity settling area is introduced into the high-radioactivity decay tank.
2. The radioactive waste fluid treatment system of claim 1, wherein the high radioactive decay tank and/or the low radioactive decay tank comprises:
a sealed decay tank for containing the supernatant liquid of the low-activity settling zone and/or the high-activity settling zone;
a decay tank inlet communicating the sealed decay tank with the low-radioactivity settling zone and/or the high-radioactivity settling zone;
the air outlet is arranged on the sealed decay tank, is communicated with the sealed decay tank and is provided with an opening and closing valve;
the medicine filling port is arranged on the sealed decay tank, is communicated with the sealed decay tank and is provided with an opening and closing valve;
a reamer disposed in the sealed decay cell;
and the decay pool outlet is communicated with the sealed decay pool and is provided with an opening and closing valve.
3. The radioactive liquid waste treatment system according to claim 2, wherein a liquid level gauge is further provided on the sealed decay tank for measuring a liquid level in the sealed decay tank.
4. The radioactive liquid waste treatment system according to claim 2, wherein the sealed decay tank is further provided with a drug filling port for adding a drug to the sealed decay tank.
5. The radioactive liquid waste treatment system according to claim 2, wherein the sealed decay tank is further provided with water jets for adding dilution and/or washing water to the sealed decay tank.
6. The radioactive liquid waste treatment system according to claim 2, wherein the sealed decay tank is further provided with a sampling port for collecting a sample from the sealed decay tank.
7. The radioactive waste liquid treatment system according to claim 2, wherein the sealed decay tank is further provided with an activity measuring pipeline for sampling and measuring the waste liquid in the sealed decay tank; and the inlet of the activity measuring pipeline is communicated with the sealed decay tank, and the outlet of the activity measuring pipeline is communicated with the outlet of the decay tank.
8. The radioactive liquid waste treatment system according to claim 1, wherein the low radioactive decay tank is connected to the low radioactive settling zone and the high radioactive settling zone based on a pipe provided with a valve.
9. The radioactive liquid waste treatment system according to claim 1, wherein the high radioactive decay tank and the low radioactive settling zone are connected based on a pipe provided with a valve.
CN202221729725.0U 2022-07-05 2022-07-05 Radioactive waste liquid treatment system Active CN218038595U (en)

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CN202221729725.0U CN218038595U (en) 2022-07-05 2022-07-05 Radioactive waste liquid treatment system

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Application Number Priority Date Filing Date Title
CN202221729725.0U CN218038595U (en) 2022-07-05 2022-07-05 Radioactive waste liquid treatment system

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